Current and Prospective Tests in Reactor MIR.M1 Alexey IZHUTOV - - PowerPoint PPT Presentation

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Current and Prospective Tests in Reactor MIR.M1 Alexey IZHUTOV - - PowerPoint PPT Presentation

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The 18th IGORR Conference 3-7 December 2017, The International Conference Centre, Darling Harbour, Sydney, Australia Current and Prospective Tests in Reactor MIR.M1 Alexey IZHUTOV INTRODUCTION Research Reactor MIR.M1 50 years in operation

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Current and Prospective Tests in Reactor MIR.M1

Alexey IZHUTOV

The 18th IGORR Conference 3-7 December 2017, The International Conference Centre, Darling Harbour, Sydney, Australia

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2 Saint Petersburg Moscow Ulyanovsk Samara 90 km 160 km Dimitrovgrad

INTRODUCTION Research Reactor MIR.M1 – 50 years in operation

– operating FA channel – experimental channel – combined operating FA with absorber – control rod channel

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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Parameter Value Nominal thermal power, МW 100 Maximal thermal neutron flux density in the loop channel, сm-2s-1 5·1014 Power operation days per year, days 230÷240 Fuel UO2 - 90% HEU Core height, mm 1000 The number of loop channels, pcs. 11 Planned life-time Till at least 2035 INTRODUCTION General Technical Data of the MIR.M1

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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INTRODUCTION Parameters of MIR.M1 Loops

Parameter

Loops

PV-1 PVK-1 PV-2 PVK-2 PVP-2 PG

Coolant

Water Water, Boiling Water Water, Boiling Water, Boiling, Steam He, N2

Number of channels

2 2 2 2 1 1

Channel capacity, kW

1500 1500 1500 1500 2000 160

Coolant temp., С

350 350 350 355 550 600

Max pressure, MPa

16,8 16,8 17,8 17,8 20,0 20,0

Max flow rate , t/h

16,0 14,0 16,0 14,0 10,0

  • The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia
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Preparation of experiments with fresh and fuel rods and spent fuel NPP

EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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Cladding

extensometer

Reactor core

Channel vessel

Cable

WWER-440 full-size

fuel rods WWER-1000 full-size fuel rods Shroud Refabricated fuel rods Refabricated fuel rod instrumented with pressure transducer and thermocouple

Irradiation rigs to test fuel and structural materials EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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Gauges for in-pile measurements installing installed in fuel rods EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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Design of interim inspection stand (a), design of ultrasonic cleaner (b), photo of interim inspection stand in the MIR.M1 storage pool (c)

a) c)

4 8 12 400 800 1200 Length, mm Oxide film, µm FR bottom FR top 9,04 9,08 9,12 9,16 400 800 1200 Length, mm Diameter, mm FR bottom FR top

*FR – fuel rod

b)

EXPERIMENTAL AND METHODICAL SUPPORT OF TESTS AND EXAMINATIONS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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KEY TRENDS IN FUEL TESTS

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Research reactor fuel Fission gas release from leaking fuel rods and Gd fuel rods with artificial defects

Normal conditions, abnormal conditions (RAMP), maneuvering, design-basis accidents (LOCA, RIA) Testing complex of fuel and core components

  • f nuclear reactors
  • f different types

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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10 Irradiation rig to test full- size and refabricated fuel rods under RAMP

Linear heat rate (LHR) vs of burnup

Amplitude of LHR at RAMP tests (R1…R12)

Elongation gauges for a fuel rod (a) and fuel column (b) a) b)

300 600 900 1200 10 20 30 40 50 60 70 LHR, W/cm Burnup, MWd/kgU

○ - Tight VVER-1000 fuel rods Δ - Tight VVER-440 fuel rods ▲ - Leaking VVER-440 fuel rod □, ■ - Experimental fuel rods (tight and leaking ones, correspondingly)

1,0 1,5 2,0 2,5 3,0 50 100 150 200 Time, m LHR, rel. units

R1 R2 R3 R4 R5 R6 R7 R8 R12

1,0 1,5 2,0 2,5 3,0 10 20 30 40 Time, h LHR, rel. units

R9 R11

RAMP TESTS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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11 Irradiation rig to test fuel rods under multiple power cycling (maneuvering) Experiment scenario Relation between elongation of the VVER-1000 refabricated fuel rods (50 MWd/kgU) and fuel temperature under power maneuvering: first 40 cycles (a); other 40 cycles, and power ramping (×) after interim storage (b) a) b)

qlmin qlmax qlmin qlmax

ql min ql max CYCLES 1st n LHR Time ql min ql max LHR CYCLES 1st n

0,0 0,2 0,4 0,6 0,8 1,0 700 900 1100 1300 1500 Temperature, °C Elongation, mm 1 10 20 30 40 0,0 0,2 0,4 0,6 0,8 1,0 700 900 1100 1300 1500 Temperature, °C Elongation, mm 41 50 70 80

Testing under Power Cycling (Maneuvering)

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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12 Irradiation rig to test a FA fragment (a) and single fuel rod (b) a) b) Temperature scenario in the experiment Change in the fuel cladding temperature (thermocouples 1, 2, 3) and coolant (thermocouples 4, 5) in the experiment

ТС 1 ТС 2 ТС 3 ТС 4 ТС 5 ТС 6 Shrou d Basket Insulato r Pressur e gauge Heater

200 400 600 800 1000 19:00 19:10 19:20 19:30 19:40 19:50 20:00 Time, h:m Temperature, °C

4 3 2 5 1

200 300 400 500 600 700 800 900

  • 300 -200 -100

100 200 300 400 500 600 Time, s

Fuel cladding temperature, °C

I II IV

V

III

Experiment temperature range

ts Up to 5 hours

LOCA TESTS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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13 Rotation by 90о Change in the fuel cladding temperature above the central (1), lower (2) and upper (3) spacer grids at 5…50 mm from the upper grid end. Change in gas pressure (4). MIR-LOCA/50 experiment State of the fuel rod after MIR-LOCA/50 experiment (X-ray)

280 360 440 520 600 680 760 840 12:00 12:01 12:02 12:03 12:04 12:05 12:06 12:07 Time, hh:mm Temperature, °C 1 2 3 4 5 6 7 Pressure, MPa 4 3 1 2

LOCA TESTS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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CMP

Irradiation rig schematic representation TC data in the fuel column: T1, T5 – refabricated fuel rods 1,2; Т4 – non-irradiated fuel rod Pulse form in the MIR.M1 reactor

1 2 3 4 5 6 2 4 6 8 10 Time, s Heat rate, rel. units

Time interval at constant power 300 600 900 1200 1500 1800 10 12 14 16 18 20 Time, s Temperature, оC 6 12 18 24 30 36 ND data, mV

Т4 Т1 Т5 ND data Т4 Т1 Т5

RIA TESTS

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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PVP-1 N2

On-line gamma spectrometer on the control

Change in the specific activity

  • f

inert radioactive gas in coolant during tests Change in the specific activity of iodine radionuclides in coolant during tests

1,00E+05 1,00E+06 1,00E+07 1,00E+08 1,00E+09 3 6 9 12 15 18 21 24 Time, days Activity, Bq/kg

Kr-85m Kr-87 Kr-88 Kr-89 Xe-133 Xe-135 Xe-138

1,00E+05 1,00E+06 1,00E+07 1,00E+08 1,00E+09 3 6 9 12 15 18 21 24 Time, days Activity, Bq/kg

I-131 I-132 I-133 I-134 I-135

Fission Product Release Investigation

  • f Leaking Fuel Rods

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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After the Fukushima accident, all RIAR’s reactors were subject to analysis of consequences from all possible

  • ff-site

impacts such as earthquake (6 grades), tornado and fire at the adjacent territory.

Key tasks to enhance the MIR.M1 safety:

  • 1. Long-term (for more than 24 hours) provision of power

for safety-important systems.

  • 2. Anti-seismic system implementation
  • 3. Abgrading the fire protection system .

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Activities to Enhance the MIR.M1 Reactor Safety

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New diesel-based emergency power supply system was put into operation Emergency power supply system modernization

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Anti-seismic system implementation

Anti-seismic system was implemented able to control the reactor building and reactor supporting structure vibrations and output signals to the emergency system in case the set threshold is exceeded. Seismic sensor CMG-5TD-М.

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New automatic fire detection and alarm system Abrading the fire protection system

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Installation of additional mobile water pumps

  • 1. Nominal pump output, ls

10,0

  • 2. Nominal pump pressure, m

60,0

  • 3. Nominal rotation frequency, rot/min

3400

  • 4. Nominal pumping head, m

1,5

  • 5. Max pumping head, m

5,0

Abrading the fire protection system

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CONCLUSIONS

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Activities to further enlarge the MIR.M1’s experimental capabilities and develop promising areas of research:  improvement of the techniques to control parameters and perform in-reactor measurements of fuel rods characteristics;  reactor tests in justification of the improved and new types of VVER and PWR fuels under different designed conditions;  use of a gas-cooled loop to examine core components and FA dummies of high-temperature gas-cooled reactors;  reactor tests to improve and justify fuels of SMR;  permanently upgrading

  • f

the MIR.M1 reactor and its equipment and extension of its lifetime, including replacement of Be blocks.

The 18th IGORR Conference, 3-7 December 2017, Sydney, Australia

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Thank you for your attention!

For further information please contact: Alexey IZHUTOV JSC “SSC RIAR” Теl.: +7(84235) 3 20 21 Web: www.niiar.ru E-mail: adm@niiar.ru